Abstract An internal parallel coupling scheme was developed for the coupling between high-fidelity neutronics code NECP-X and the sub-channel thermal-hydraulic code CTF. A new coupling iteration scheme is proposed based on NECP-X/CTF, in which CTF will run after each transport sweep of NECP-X. The interface is developed for both CTF and NECP-X to transfer data via memory rather than files. Based on the newly developed high-fidelity neutronics/thermal-hydraulic coupling system NECP-X/CTF, the impact of the hydraulic cross-flow model, heat conduction model and gap conductance model was studied by calculating the VERA hot full power assembly and core cases. The numerical results show that the internal parallel coupling method is an effective approach for reactor core coupling simulation for the steady state calculation, the new coupling iteration method is more efficient than the traditional Picard iteration method. The sensitivity analysis demonstrates that the cross-flow and gap conductance are very important in coupling for the neutronics and thermal-hydraulic coupling.

中文翻译：

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基于NECP-X和CTF的内部并联耦合方法及热工水力模型对高保真计算的影响分析

摘要 针对高保真中子码NECP-X与子通道热工水力码CTF之间的耦合，提出了一种内部并行耦合方案。基于NECP-X/CTF提出了一种新的耦合迭代方案，其中CTF将在NECP-X的每次传输扫描后运行。该接口是为 CTF 和 NECP-X 开发的，用于通过内存而不是文件传输数据。基于新开发的高保真中子/热液耦合系统NECP-X/CTF，通过计算VERA热全功率组件和堆芯，研究了液压错流模型、热传导模型和间隙传导模型的影响案件。数值结果表明，内并联耦合法是一种有效的堆芯耦合模拟方法，用于稳态计算，新的耦合迭代法比传统的皮卡德迭代法效率更高。敏感性分析表明，错流和间隙电导对于中子学和热液耦合的耦合非常重要。